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A list of all pages that have property "Title" with value "BWRVIP-100 Nonconservatism Affidavit". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML11208B981  + (BWROG-TP-09-033, Rev. 1, Generic Methodology for JOG MOV Periodic Verification Program - Category D MOV Evaluations)
  • ML11326A243  + (BWROG-TP-11-022, Rev. 1, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors)
  • ML11325A074  + (BWROG-TP-11-032, Report No. 0900876.401, Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations)
  • ML13022A437  + (BWROG-TP-13-001, Rev. 1, Plant Evaluation of Severe Accident Mitigation Strategies)
  • ML14077A091  + (BWROG-TP-13-008, Rev. 0, Containment Accident Pressure Committee (344) Task 2 - Equation for Pump Speed Correction (Cvic Pump), Attachment 9)
  • ML14077A102  + (BWROG-TP-13-009, Rev. 0, Containment Accident Pressure Committee (344) Task 3 Pump Operation at Reduced Npsha Conditions (Cvic Pump), Attachment 10)
  • ML14077A092  + (BWROG-TP-13-010, Containment Accident Pressure Committee (344) Task 6 - Npshr Test Instrument Accuracy Effect on the Published Results (Cvic Pump), Attachment 13)
  • ML14077A093  + (BWROG-TP-13-011, Containment Accident Pressure Committee (344) Task 5 Effects of Non-Condensable Gases on Seals (Cvic Pump), Attachment 12)
  • ML14077A090  + (BWROG-TP-13-021, Rev. 0, Containment Accident Pressure Committee (344) Task 4 - Operation in Maximum Erosion Rate Zone (Cvic Pump), Attachment 11)
  • ML14077A095  + (BWROG-TP-14-001, Rev. 0, Containment Accident Pressure Committee (344) Task 1 - Cfd Report and Combined Npshr Uncertainty for Browns Ferry/ Peach Bottom Cvic RHR Pumps, Attachment 8)
  • ML032810775  + (BWROG/USNRC-Summary of Meeting Option 3, Loss-of-Coolant Accident/Loss-of-Offsite Power Risk-Informed Implementation)
  • ML20282A128  + (BWRVIP 25 Rev 1-A Withholding Determination Draft Comments (Epdi: L-2020-TOP-0017))
  • ML070610457  + (BWRVIP Actions in Response to Flaw Indications in Recirculation Inlet Piping Nozzle to Safe End Welds at Duane Arnold)
  • ML22321A153  + (BWRVIP Docket No. 99902016 - BWRVIP 2021 Inspection Summaries)
  • ML24191A244  + (BWRVIP Docket No. 99902016-BWRVIP-315-A: BWR Vessel and Internals Project, Reactor Internals Aging Management Evaluation for Extended Operations)
  • ML18115A065  + (BWRVIP Integrated Surveillance Program Subsequent License Renewal Agenda)
  • ML21266A227  + (BWRVIP Response to BWRVIP 315 Draft SE)
  • ML25169A331  + (BWRVIP Response to BWRVIP-100, Revision 2 Draft Safety Evaluation)
  • ML24131A044  + (BWRVIP Response to BWRVIP-100, Revision 2 Request for Additional Information (Rais))
  • ML25169A335  + (BWRVIP Response to BWRVIP-138, Revision 2 Draft Safety Evaluation)
  • ML21047A085  + (BWRVIP Response to BWRVIP-315 Request for Additional Information (Rais))
  • ML21056A195  + (BWRVIP Response to BWRVIP-315 Request for Additional Information (Rals))
  • ML21312A543  + (BWRVIP-100)
  • ML21312A544  + (BWRVIP-100 Nonconservatism LIC-504)
  • ML24233A095  + (BWRVIP-100 RAI Slides for Public Meeting)
  • ML23214A069  + (BWRVIP-100, Rev 2, Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds - NRC 898,Topical Report Completeness Determination)
  • ML23214A072  + (BWRVIP-100, Rev 2, Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds - NRC 897, Topical Report Withholding Determination)
  • ML23048A259  + (BWRVIP-100, Rev. 2: Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components NRC – EPRI Closed Meeting)
  • ML25202A122  + (BWRVIP-100, Revision 2 - NRC Form 896, - a Topical Report Verification)
  • ML23198A335  + (BWRVIP-100NP, Rev. 2, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components)
  • ML100480184  + (BWRVIP-117-A: BWR Vessel and Internals Project, RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5)
  • ML032230313  + (BWRVIP-117: BWR Vessel & Internals Project, RAMA Fluence Methodology Plant Application - Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5)
  • ML100480185  + (BWRVIP-117NP-A: BWR Vessel and Internals Project - RAMA Fluence Methodology Plant Application-Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5, Final Report)
  • ML17018A153  + (BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program Data Source Book and Plant Evaluations)
  • NG-16-0042, BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations  + (BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations)
  • ML24323A111  + (BWRVIP-138 Revision 2 RAIs - Short Delay)
  • ML25154A237  + (BWRVIP-138, Rev. 2: Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines)
  • ML23299A296  + (BWRVIP-138, Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines, Revision 2 - NRC 897, Withholding Determination)
  • ML23299A295  + (BWRVIP-138, Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines, Revision 2 - NRC 898, Completeness Review)
  • ML072850122  + (BWRVIP-145NP, BWR Vessel and Internals Project, Evaluation of Susquehanna Unit 2 Top Guide and Core Shroud Material Samples Using RAMA Fluence Methodology)
  • ML20353A175  + (BWRVIP-167, Revision 4: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables)
  • ML090550635  + (BWRVIP-199: BWR Vessel and Internals Project, Testing and Evaluation of the Monticello 300 Degree Capsule - Cover Letter)
  • ML090550636  + (BWRVIP-199NP, BWR Vessel and Internals Project, Testing and Evaluation of the Monticello 300 Degree Capsule, 1016567NP Final Report)
  • ML18040A505  + (BWRVIP-234NP-A: BWR Vessel and Internals Project, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steels for BWR Internals)
  • ML11171A037  + (BWRVIP-25 Core Plate Bolt Stress Analysis)
  • NLS2003028, BWRVIP-25 Rim Hold Down Bolt Inspection Deferral  + (BWRVIP-25 Rim Hold Down Bolt Inspection Deferral)
  • ML20282A127  + (BWRVIP-25, Rev 1 - a Verification Form)
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